US3656566A - Gas cooled nuclear reactor installation - Google Patents

Gas cooled nuclear reactor installation Download PDF

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Publication number
US3656566A
US3656566A US764707A US3656566DA US3656566A US 3656566 A US3656566 A US 3656566A US 764707 A US764707 A US 764707A US 3656566D A US3656566D A US 3656566DA US 3656566 A US3656566 A US 3656566A
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US
United States
Prior art keywords
coolant
reactor
nuclear reactor
moderator
channels
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
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US764707A
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English (en)
Inventor
Geoffrey Coast
Vernon Morgan
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UK Atomic Energy Authority
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UK Atomic Energy Authority
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/328—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the prime mover is also disposed in the vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention concerns a gas cooled nuclear reactor station and is especially concerned with a gas-cooled graphite moderated nuclear reactor station wherein the gaseous coolant leaving the reactor core is passed through a gas turbine to a regenerative heat exchanger wherein it gives up most of its residual heat to coolant returning to the reactor core at boosted pressure, after which the returning coolant is then reduced by a further gas turbine before the said returning gaseous coolant re-enters the reactor core.
  • the outlet temperature of the further gas turbine if the cycle is to be eflicient, is higher than that desirable for the reactor core to operate at continuously. Whilst the outlet temperature can be reduced, it can only be reduced at a heavy price in the efficiency of the cycle.
  • the critical parts of the reactor core are the graphite blocks that form the moderator and reflector structure which are normally cooled by a fraction of the coolant separated from the main stream on entry to the reactor core.
  • a closed coolant circuit of a gas cooled nuclear reactor installation comprising a reactor core, a heat utilisation plant, a multi-stage compressor for circulating coolant through said circuit and a coolant feed heater, there is a bleed duct by-passing the feed heater to lead some of the coolant at a relatively low temperature to cool moderator components of the core.
  • Nuclear reactor fuel elements are capable of prolonged operation at high temperatures and as far as the fuel elements are concerned there is no objection to the coolant entering the core at temperatures of 400500 C and at a pressure of say 1030 pounds per square inch. This applies even to graphite sleeves round the fuel elements as these are replaced periodically (when the fuel charge is changed). However permanent graphite structure would deteriorate under such conditions and should be kept at a temperature of about 340 C.
  • coolant at a lower temperature is preferably used in a graphite moderated reactor to cool the graphite moderating core structure. It can also be used to cool the nuclear reactor pressure vessel wall and diaphragrns extending across the pressure vessel where they exist as in the later versions of the British AGR. In this way savings can be made in the cost of thermal insulatron.
  • the invention is especially applicable to reactor installations as described in British Pat. No. 1,058,518 and US. Pat. application Ser. No. 722,929, filed on Apr. 22, 1968 where CO is compressed by a multi-stage compressor to say 2200 pounds per square inch within a temperature range of between say -l00 C at which temperature range the necessary power is comparatively small and then preheated and then expanded through a gas turbine.
  • the bleed duct can tap off from an intermediate point in the compressor at a temperature of say 59 C and a pressure of say 1040 pounds per square inch. It has been calculated that an 8 /2% bleed would be sufficient in one design to maintain the permanent graphite moderating core structure at the desired temperature.
  • the coolant channels through the moderating core structure should converge in the direction of flow, possibly in a stepwise manner. This convergence results in poorer heat transfer where the coolant channels are larger.
  • FIG. 1 is a schematic arrangement of a gas cooled reactor coolant circuit
  • FIG. 2 is a plan view on a nuclear reactor installation
  • FIG. 3 shows an alternative feature of the arrangement shown in FIG. 1
  • FIG. 4 is an illustration of a re-entrant coolant passage in a moderating core structure of a reactor
  • FIG. 5 is a partial section in elevation through the nuclear reactor station along 5-5 of FIG. 2.
  • carbon dioxide is used in a closed circuit as coolant gas for a graphite moderated nuclear reactor core.
  • the gas leaves the reactor core 25 by way of a port 25c at a pressure of 1005 pounds per square inch, a temperature of 700 C and a density of 2.3 pounds per cubic foot, and is passed through a first turbine stage 11, by which electrical power is produced.
  • the coolant gas On exhausting from the turbine stage 11 at a pressure of 405 pounds per square inch, the coolant gas has its temperature reduced from 585 C to 120 C in a feed heater 12 which is made in two parts joined by a concentric duct 13.
  • the coolant is cooled further to 25 C in a precooler 14 and then undergoes compression in a three stage compressor 15 which cooperates with interstage coolers 16a to provide a first fraction of coolant leaving the compressor at a pressure of 2200 pounds per square inch and a temperature of C to flow to the feed heater 12.
  • the temperature of the first fraction is increased to 495 C in the feed heater l2 and the pressure is then reduced to 1030 pounds per square inch in a turbine 16 used to drive the compressor 15.
  • the first fraction is then returned to the nuclear reactor core to have its store of heat replenished prior to repeating the cycle.
  • the core at present envisaged is of the type known as the British Advanced Gas-Cooled reactor wherein there is a moderating core structure which is kept relatively cool.
  • a second fraction of coolant, hereinafter termed re-entrant moderator coolant is taken from the output of one of the compressor stages at a pressure of say 1,100 pounds per square inch and a temperature of about 60 C by means of a duct 10 and, by-passing the feed heater 12, is directed to the reactor to cool the moderating core structure.
  • the moderating core structure comprises a plurality of columns of stacked graphite blocks which define vertical passageways for moderator cooling channels and fuel element channels.
  • the moderator coolant flow channels are designated 35 and the fuel element channels are designated 26b.
  • a first inlet port connected to the moderator cooling channels is designated 35c.
  • Moderator coolant flows downwardly through the passages 35 and rejoins the main stream of the coolant at the bottom of the core, the coolant then flowing up the fuel element channels 26b.
  • the reactor installation is built on a monolithic concrete raft 22 having three station output generators 23 on platforms 23a about its periphery. On this raft rests, as shown in FIG. 2, the concrete pressure vessel 19. This vessel is lobed with one of the three parallel sub circuits associated with a corresponding lobe.
  • This raft is housed inside a building 24 which provides the usual reactor facilities such as a fuel handling area 25a, a services block 26a, and electrical transformer compound 27a.
  • FIG. 5 is a section through the wall of the pressure vessel showing part of the core of the reactor.
  • the inside or vault of the pressure vessel and the core are very similar to that described in US. Pat. application Ser. No. 685,874 filed on Nov. 27, 1967.
  • a moderating core structure 25 is supported in columns 26 of block like components on a layer 27 of plates which rest on pillars 28.
  • the core is constrained against outward movement by restraints 29 on the vessel.
  • a steel diaphragm 30 separating the coolant inlet and coolant outlet above the core proper carries laterally resilient devices 31.
  • the return flow of coolant gas from the compressor 16 to the reactor core enters a plenum 48 (FIG. 5) by way of a duct 49.
  • the moderator coolant fraction from the compressor 15 returns by way of duct to the vault housing the core, expands over the peripheral surfaces of the core, flows to beneath the diaphragm 30, thence downwardly through the channels 35 to the plenum 48 where it reunites with the main flow of reactor coolant.
  • the reactor coolant then flows upwardly in heat exchange with the fuel through channel extensions which penetrate the diaphragm 30 and which open into the coolant outlet from the reactor.
  • a gas cooled nuclear reactor installation comprising a closed coolant circuit having a plant for utilizing heat energy, a reactor core having a solid moderator with fuel element channels containing fuel elements and moderator cooling channels, a first coolant inlet port connected to said fuel element channels and a second coolant inlet port connected to said moderator cooling channels, and an outlet port common to all of the channels, said reactor being included in said closed coolant circuit, such that the plant utilizes heat energy derived from said core, a multi-stage compressor arranged to circulate coolant through said circuit, a feed heater arranged to heat a first fraction of coolant flowing from said compressor to said first coolant-inlet port of the reactor, and a duct means for directing a second fraction of coolant flowing from said compressor to said second coolant port of the reactor, said duct by-passing the feed heater.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Particle Accelerators (AREA)
  • Turbine Rotor Nozzle Sealing (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
US764707A 1967-10-27 1968-10-03 Gas cooled nuclear reactor installation Expired - Lifetime US3656566A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB4905667 1967-10-27

Publications (1)

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US3656566A true US3656566A (en) 1972-04-18

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US764707A Expired - Lifetime US3656566A (en) 1967-10-27 1968-10-03 Gas cooled nuclear reactor installation

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US (1) US3656566A (enrdf_load_stackoverflow)
CH (1) CH483694A (enrdf_load_stackoverflow)
DE (1) DE1804025A1 (enrdf_load_stackoverflow)
FR (1) FR1589333A (enrdf_load_stackoverflow)
GB (1) GB1226537A (enrdf_load_stackoverflow)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3998057A (en) * 1974-02-01 1976-12-21 Hochtemperatur-Reactorbau Gmbh Nuclear powerplant with closed gas-cooling circuit
US4036689A (en) * 1974-11-23 1977-07-19 Hochtemperatur-Reactorbau Gmbh Multichamber hydrogen generating plant heated by nuclear reactor cooling gas
US4045285A (en) * 1974-11-23 1977-08-30 Hochtemperatur-Reactorbau Gmbh. Plant for the production of hydrogen through utilization of heat energy obtained from a gas-cooled nuclear reactor
US4120750A (en) * 1974-12-19 1978-10-17 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Nuclear energy plant with closed working gas circuit
US4343681A (en) * 1974-07-23 1982-08-10 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Core energy plant with closed working gas circuit
US20250243764A1 (en) * 2010-09-21 2025-07-31 8 Rivers Capital, Llc High efficiency power production methods, assemblies, and systems

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3377800A (en) * 1965-08-12 1968-04-16 Escher Wyss Ag Nuclear reactor gas-turbine plant with emergency cooling
US3410091A (en) * 1964-10-07 1968-11-12 Escher Wyss Ag Nuclear thermal power plant
US3444038A (en) * 1966-07-09 1969-05-13 Siemens Ag Nuclear power station with carbon dioxide cooling system

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3410091A (en) * 1964-10-07 1968-11-12 Escher Wyss Ag Nuclear thermal power plant
US3377800A (en) * 1965-08-12 1968-04-16 Escher Wyss Ag Nuclear reactor gas-turbine plant with emergency cooling
US3444038A (en) * 1966-07-09 1969-05-13 Siemens Ag Nuclear power station with carbon dioxide cooling system

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3998057A (en) * 1974-02-01 1976-12-21 Hochtemperatur-Reactorbau Gmbh Nuclear powerplant with closed gas-cooling circuit
US4343681A (en) * 1974-07-23 1982-08-10 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Core energy plant with closed working gas circuit
US4036689A (en) * 1974-11-23 1977-07-19 Hochtemperatur-Reactorbau Gmbh Multichamber hydrogen generating plant heated by nuclear reactor cooling gas
US4045285A (en) * 1974-11-23 1977-08-30 Hochtemperatur-Reactorbau Gmbh. Plant for the production of hydrogen through utilization of heat energy obtained from a gas-cooled nuclear reactor
US4120750A (en) * 1974-12-19 1978-10-17 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Nuclear energy plant with closed working gas circuit
US20250243764A1 (en) * 2010-09-21 2025-07-31 8 Rivers Capital, Llc High efficiency power production methods, assemblies, and systems

Also Published As

Publication number Publication date
FR1589333A (enrdf_load_stackoverflow) 1970-03-23
GB1226537A (enrdf_load_stackoverflow) 1971-03-31
CH483694A (de) 1969-12-31
DE1804025A1 (de) 1969-07-03

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